BACKGROUND OF THE INVENTION1. Field of Invention
The present invention relates to determination of water saturation in subsurface formations surrounding a well borehole using radioactivity well logging.
2. Description of Prior Art
In evaluating reservoirs as possible candidates for enhanced recovery programs, it is important to determine residual oil saturation of the earth formations adjacent well boreholes. The accurate determination of water saturation in reservoir formations was a requisite to determining oil saturation for locating new reserves in old wells. A high degree of accuracy was particularly important when determining whether or not to commence expensive enhanced recovery projects. It was a desirable goal to determine oil saturation to within ±3 saturation units.
In the past, pulsed neutron sources have been used to bombard the formations and measure from the response of the formations the macroscopic thermal neutron capture cross section, Σ, of the formation. When the formation porosity, shale fractional volume and thermal neutron capture cross-section of the shale and rock matrix were known, the thermal neutron capture cross-section of the fluid, Σf, could be determined. From the value of Σf, a measure of water saturation was obtained. However, errors in the values of the parameters used in determining water saturation limited the accuracy of this method.
Log-inject-log techniques have been developed to eliminate some of the parameters in determining residual oil saturation. These techniques involved successive logging after modification of the formation fluids by various injection methods. However, the accuracy of these techniques was still less than desirable.
Another method of determining water saturation is disclosed in U.S. Pat. Nos. 3,930,153 and 3,930,154, of which Applicant is inventor, which utilized capture gamma spectroscopy logging. A NaI (T1) gamma ray detector sensed gamma radiation from thermalized neutrons originally emitted by a pulsed neutron source. The gamma ray spectra of the formation were recorded and then analyzed for the presence of chlorine and hydrogen. The analysis was complex, requiring a least squares fit of the formation spectra to a postulated formation spectra.
SUMMARY OF INVENTIONBriefly, the present invention provides a new and improved method of determining the water saturation of an earth formation surrounding a well borehole. From the water saturation, the oil saturation or relative presence of oil in the formation may be determined.
According to the present invention, repetitive pulses of fast neutrons bombard the earth formation, are slowed down and thereafter engage in neutron capture reactions with materials in the vicinity of the borehole. A germanium gamma ray detector obtains gamma ray spectra from thermal neutron capture reactions by chemical elements of the materials in the formation. The gamma ray detector is preferably formed from intrinsic germanium, that is, germanium as pure as is physically realizable, and is cooled to a low temperature, such as approximately -190° C., or near the temperature of solid propane.
The thermal neutron capture gamma ray spectra are then processed to obtain a measure of the relative presence of chlorine to that of hydrogen in the formation. From the measure of the relative presence of chlorine and hydrogen, the apparent water salinity of the formation under investigation is determined. Thereafter, the apparent water salinity and the true water salinity, which may be obtained from well production data or from a formation at a lower depth in the borehole having known water salinity, are used to obtain the water saturation of the formation under investigation.
BRIEF DESCRIPTION OF THE DRAWINGSFIG. 1 is a schematic block diagram of a well logging system according to the present invention;
FIG. 2 is a timing diagram representing the relative time occurrence of neutron emission times and measurement or count time gates of gamma ray spectra according to the present invention;
FIG. 3 is a diagram of total gamma ray counts, displayed on a logarithmic scale as a function of time;
FIG. 4 is a diagram of capture gamma ray counts as a function of their energy levels during the count gate of FIG. 2;
FIG. 5 is a logic flow diagram of a process suitable for performance in a computer according to the present invention; and
FIG. 6 is a graphical representation of the relation between the chlorine/hydrogen ratio of a formation determined according to the present invention and the water salinity of the formation.
DESCRIPTION OF PREFERRED EMBODIMENTIn FIG. 1 of the drawings, the apparatus of the present invention is shown in aborehole 10 in anearth formation 12. Theformation 12 is lined in a conventional manner with asteel casing 14 or the like. A well logging system S is, according to the present invention, adapted to examine and investigate water saturation characteristics of theearth formation 12 is shown with portions thereof in theborehole 10.
Considering the logging system S more in detail, an elongated, fluid tight hollow body member orsonde 16 is adapted to be passed longitudinally through thecasing 14. A control and processing apparatus designated generally as P, is located at the surface for processing and recording electrical measurements, obtained in a manner to be set forth below, provided by components within thesonde 16. Alogging cable 18 is passed over asheave wheel 20 to support thesonde 16 in theborehole 10. Thecable 18 contains one or more conductors for transmitting electrical signals formed in components within thesonde 16 to the surface equipment P.
Thesonde 16 contains asource 22 of high energy neutrons. The neutron source preferred for use in the present invention comprises a deuterium-tritium reaction accelerator. However, it should be understood that other neutron sources available for well logging may also be utilized as thesource 22 according to the present invention. Examples are Americium-beryllium, actinium227 -beryllium, and californium252. As will be set forth below, according to the present invention, theneutron source 22 is activated to emit high energy neutron pulses for a predetermined interval so that theearth formations 12 are bombarded intermittently by neutrons from thesource 22.
Thesource 22 is connected to apulsing circuit 24 of conventional design, which is activated periodically by agating circuit 26, causing thesource 22 to emit a pulse of neutrons for a specified time duration beginning at a predetermined time. The pulse of neutrons emitted by the source oraccelerator 22 in response to thepulsing circuit 24 andgating circuit 26 irradiates theearth formation 12 intermittently with neutron pulses beginning at a time t0 (FIG. 2) and lasting until a time t1, of typically twenty microseconds, at a frequency of from five hundred to one thousand times per second.
Aradiation detector 28 for detecting capture gamma rays resulting from bombardment of theearth formation 12 surrounding theborehole 10 is illustrated schematically in the drawings contained within avacuum container 30. According to the present invention, thedetector 28 is formed from intrinsic germanium. For the purposes of the present invention, intrinsic germanium is defined as germanium which is as close to purity as is physically realizable. Thegermanium detector 28 is cooled in thevacuum container 30 by a suitable coolant, such as solid propane, to a low temperature such as approximately -190° C., or near the temperature of liquid nitrogen. It is important to note that with an intrinsic germanium detector according to the present invention, it is possible to temperature cycle such crystal. Accordingly, it is no longer necessary to maintain the detector at the low temperature when thesonde 16 is not in use. Further, with thegermanium detector 28 according to the present invention, discrete and highly accurate detection of thermal neutron capture gamma ray peaks, when plotted as a function of gamma ray energy, may be obtained, permitting highly accurate processing of the well logging data in the processing apparatus P in order to determine water saturation of theformation 12.
Thedetector 28 is shielded from thesource 22 by aradiation shield 32 of suitable composition, such as a high hydrogen content material containing a combination of lead, iron, lucite plastic, or the like in order to prevent or substantially reduce direct irradiation of thedetector 28 as a result of emission of neutrons from theaccelerator 22.
Thedetector 28 generates a voltage pulse which is functionally related to the energy of the gamma rays received so that each pulse generated in thedetector 28 has an amplitude functionally related to the energy of the corresponding gamma ray causing such pulse. Anamplifier 34 is electrically connected to thedetector 28 through suitable seals formed in thevacuum container 30 to amplify the electrical signals formed in thedetector 28. A conventional discriminator or bias level circuit 36 may be connected, if desired, to theamplifier 34 in order to reduce spurious signals due to neutron activation of thedetector 28 by stray neutrons from thesource 22. Anamplifier 38 receives the output from the discriminator 36 and is electrically coupled by a suitable conductor to acable driver amplifier 40 so that output signals from thedetector 28, after passing through theamplifier 34 and discriminator 36, are permitted to pass through conductors in thecable 18 to the processing instrumentation P at the surface.
Accordingly, the capture gamma ray response of theearth formation 12 to the pulsed neutrons from theaccelerator 22 may be measured at selected time intervals, as will be set forth, relative to the emission of neutrons from thesource 22. Thecable driving circuit 40 is of conventional function and structure and provides power to transmit the response from the discriminator circuit 36 to the surface instrumentation P. Further, although not shown, it should be understood that conventional power supplies are included in the present invention for operating the surface instrumentation P and the circuitry contained in thesonde 16, as well.
Electrical signals from thedownhole sonde 16 passed through thecable 18 are received at acount gate 42 and abackground gate 44 operating in response to control signals formed in a surfaceclock control network 46. Thecontrol network 46 is a conventional actuating circuit having circuitry therein to cause emission of timing pulses causing thegates 42 and 44 to operate in synchronism with each other and in synchronism with thegating circuit 26 in thesonde 16. Thegates 42 and 44 are individually activated at different times by thecontrol network 46 to permit readings of the thermal neutron capture gamma ray population to be made during time intervals when thedetector 28 detects radiation while theaccelerator 22 is quiet. Thecount gate 42 is activated at a time t2 (FIG. 2) sufficiently long after the emission of neutron bursts from thesource 22 to permit the rapid absorption effect of the borehole materials to die away, and further to permit the emitted neutrons to reach the thermal energy level before measurements are taken. A suitable example of time t2 after the time t0 would be on the order of four hundred microseconds. Thecount gate 42 is typically activated for a time on the order of five hundred to seven hundred microseconds.
Background gate 44 is activated at a time t4 sufficiently long after the emission of each neutron burst to permit the thermal neutrons to be substantially all absorbed so that the remaining radiation present in the formation and the tool comprises residual or background radiation. A display curve 48 (FIG. 3) illustrates an example plot of the number of gamma rays, displayed logarithmically as a function of time, present in theborehole 10. The origin time for thedisplay curve 48 occurs at the time t0 (FIG. 2) when the emission of neutrons from thesource 22 commences. As is evident from thecurve 48, the number of gamma rays rapidly decreases due to borehole effects and thereafter undergoes an exponential decrease due to capture of neutrons during the time interval when thecount gate 42 is activated, and thereafter decreases until the time interval when thebackground gate 44 is activated when only background or residual radiation is present.
The count signals passing through thecount gate 42 andbackground gate 44 are provided to apulse height analyzer 50 which sorts and accumulates a running total of incoming pulses into memory storage locations based on the height or amplitude of the incoming pulses. Thepulse height analyzer 50, as is conventional, forms a cumulative record of the number of pulses occurring at each energy level or channel, typically expressed in Mev. Thepulse height analyzer 50 may, if desired, be electrically connected to asuitable recording apparatus 52, such as a tape recorder, in order to store therein the record of the total of incoming pulses accumulated in thepulse height analyzer 50 as a function of depth of thesonde 16 in theborehole 10. In this manner, the signals recorded in therecorder 52 may be returned to thepulse height analyzer 50 for use at a later time or for processing and comparison with other data, if desired.
A display 54 (FIG. 4) indicates an example gamma ray spectrum as a function of Mev energy forgate 42. Attention is directed to the prominent peaks observed, due to the utilization of the cooledintrinsic germanium detector 28 in thesonde 16, resulting from thermal neutron capture in hydrogen (water and oil), chlorine (salt water), silicon (quartz) and iron (borehole steel casing). Further, the highly pronounced peaks at lower gamma ray energies illustrate the efficiency of the germanium gamma ray detector according to the present invention at lower gamma ray energies.
Thus, with the present invention, highly pronounced and prominent capture gamma ray count peaks are obtained for gamma ray energy levels or channels indicative of particular chemical elements in thewell borehole 10 and in theformation 12. These peaks rise exaggeratedly above a continuum or gradually decreasing average indicated by the count levels between peaks and phantom lines beneath the peaks in FIG. 4.
With the present invention, by the use of the cooledgermanium detector 28 ananalysis computer 58 may process the data stored in thepulse height analyzer 50 in accordance with a sequence of steps (FIG. 5) to obtain a measure of the water saturation of theformation 12 under investigation. Arecorder 60 is connected to thecomputer 58 to form a record of the results of processing so that such results may be available for later use or analysis. Aplotter 62 is connected to therecorder 60 so that output records of the water saturation in theformation 12 as a function of depth in theborehole 10 are available for analysis in determining whether to initiate secondary or tertiary recovery operations in the formations of interest. The analysis computer may be, for example, a PDP-11 Minicomputer typically a part of field well logging equipment. Due to the accuracy of the measurements obtained with thedetector 28, relatively simple processing is permitted, and field processing of the data is thus possible.
A flow chart F (FIG. 5) sets forth the sequence of steps of controlling thecomputer 58 in a manner sufficient to enable one of skill in the art to process the data obtained with thedetector 28 and stored in thepulse height analyzer 50 by writing computer language instructions, such as in the FORTRAN program language or other suitable computer language to process such data.
During an initial operation step 70 (FIG. 5), thecomputer 58 extracts the counts for each of the channels in thepulse height analyzer 50 and subtracts the gamma ray continuum, of the type set forth above, from each of such channels, effectively removing all but the peaks detected by thedetector 28 from the data to be processed. The background radiation measurement obtained by thegate 44 is also subtracted during thestep 70.
Thecomputer 58, under control of an instruction 74 then compensates for iron in the casing and for hydrogen and chlorine in thewell borehole 10. Processing under control of instruction 74 by thecomputer 58 may be accomplished, for example, in accordance with the techniques dislosed in U.S. Pat. No. 3,930,154, so that the effect of iron in the casing and hydrogen and the chlorine in the well borehole on the data stored in thepulse height analyzer 50 are removed to permit more accurate measurement of the chlorine and hydrogen in the formation and thus more accurate determination of the water saturation of the formation.
Thecomputer 58, under control of an instruction 76, then determines a measure of the relative presence of chlorine to hydrogen by comparing the area under two gamma ray energy peaks, one for chlorine and one for hydrogen. Due to the efficiency of thegermanium detector 28 at low gamma ray energies, suitable peaks for determining the chlorine to hydrogen or Cl/H ratio are to 2.223 Mev peak for hydrogen and the 1.953 Mev peak for chlorine. However, where the formations are known to contain limestone, dolomite, anhydrite or gypsum, and thus calcium, an interfering calcium peak would be present at 1.944 Mev. In this situation, a different chlorine peak, such as a chlorine peak at 1.163 Mev could be used.
Once the Cl/H ratio has been determined during step 76, the apparent formation water salinity is determined during thestep 78. The determination may readily be made by consulting a computer memory location or by reference to a chart 80 (FIG. 6) obtained from a known test formation setting forth water salinity in parts per million as a function of chlorine/hydrogen ratio of salt water.
After the apparent formation water salintiy is determined, the water saturation Sw is then obtained by thecomputer 58 under control of aninstruction 82. Water saturation Sw in a formation is determined by the ratio of the apparent formation water salinity to the true salinity, or expressed as an equation:
S.sub.w =apparent salinity/true salinity
The true salinity may be obtained from production data obtained during production of oil in the well or may be obtained from water salinity readings obtained in a lower zone known to be one hundred percent water saturated. Once the water saturation Sw is obtained in the manner set forth above, and where no gas is present in the reservoir being tested for water saturation, the oil saturation So may be obtained by using the following equation:
S.sub.o =1-S.sub.w
Accordingly, the method of the present invention has significant application and impact in determining residual oil saturation in reservoirs to determine which reservoirs are suitable for enhanced recovery programs. Further, since fewer measurements are needed according to the present invention than with the prior art, more accurate measurements may be obtained.
A further and additional advantage to determining water saturation according to the present invention arises from utilization of a ratio, namely Cl/H, rather than computation of a single number. Measurement of such a ratio has advantages over measurement of an absolute quantity since the effect of some factors on the two components on the ratio will cancel each other. For instance, the ratio Cl/H is independent of porosity φ and also independent of thermal neutron absorbers such as boron and shale.
Where thecasing 14 was cased with cement originally mixed with salt water, an additional small correction for salt water bound in the cement annulus around thecasing 14 may be desirable. A test to determine the necessity of such a correction can be made by injecting fresh water into the formation being tested to displace the salt water from the formation and from the borehole casing. Thesource 22 would then be activated and gamma ray spectra obtained utilizingdetector 28 and analyzing the spectra so obtained for chlorine peaks. If chlorine peaks are measurable in this condition, such peaks would indicate the presence of salt water in the cement surrounding thecasing 16 and compensation made therefor. Further, a small correction to the hydrogen measurement might become necessary if the formation contains a substantial amount of shale, which contains some bound water, but the magnitude of such a correction would be generally insignificant.
It should be understood that the foregoing embodiment is the preferred embodiment of the present invention, although numerous modifications, adjustments, changes in the program language or flow chart format, or the data output format, all coming within the scope of the appended claims, will occur to those of ordinary skill in the art.